Proton elastic scattering and proton induced γ-ray emission cross-sections on Na from 2 to 5 MeV

Differential cross-sections for proton elastic scattering on sodium and for γ-ray emission from the reactions ²³Na(p,p′γ)²³Na (E_γ = 440 keV and E_γ = 1636 keV) and ²³Na(p,α′γ)²⁰Ne (E_γ = 1634 keV) were measured for proton energies from 2.2 to 5.2 MeV using a 63 μg/cm² NaBr target evaporated on a self-supporting thin C film.The γ-rays were detected by a 38% relative efficiency Ge detector placed at an angle of 135° with respect to the beam direction, while the backscattered protons were collected by a Si surface barrier detector placed at a scattering angle of 150°. Absolute differential cross-sections were obtained with an overall uncertainty estimated to be better than ±6.0% for elastic scattering and ±12% for γ-ray emission, at all the beam energies.To provide a convincing test of the overall validity of the measured elastic scattering cross-section, thick target benchmark experiments at several proton energies are presented.     

K-shell X-ray fluorescence cross-sections and intensity ratios for some pure metals at 59.5 and 123.6 keV

K-shell X-ray fluorescence cross-sections for some pure metals such as Cr, Fe, Co, Cu, Zn, Ga, Se, Y, Mo, Cd, In, Sn, Te, Ba, Ta, W and Bi have been theoretically and experimentally determined. The Cr, Fe, Co, Cu, Zn, Ga, Se, Y, Mo, Cd, In, Sn, Te and Ba metals were excited by 59.5 keV γ-ray from 50 mCi ²⁴¹Am radioactive source and the Ta, W and Bi targets were excited by 123.6 keV γ-ray from 25 mCi ⁵⁷Co radioactive source. The characteristic K X-rays emitted by samples were detected by using a super Si(Li) detector having a resolution of 150 eV at 5.9 keV. In addition, the I_Kβ/I_Kα intensity ratios for these metals were studied. The obtained experimental values of the K-shell X-ray fluorescence cross-sections and the I_Kβ/I_Kα intensity ratios have been compared with theoretical values. The measured values were in good agreement with theoretical values.     

裂变气体核素γ射线效率刻度中的自吸收校正

针对裂变气体核素HPGe探测器效率刻度中的自吸收校正问题,本工作详细描述了源盒、探测器和源物质等计算中需要的参数,按照实际的几何布局建立了HPGe探测器效率的蒙特卡罗计算模型,并编制了相应计算程序。计算模型可靠性得到实验数据的验证,用该模型计算了裂变气体核素在不同源介质下的探测效率,得到了相应的自吸收校正因子。     

Barium-borate-flyash glasses: As radiation shielding materials

The attenuation coefficients of barium-borate-flyash glasses have been measured for γ-ray photon energies of 356, 662, 1173 and 1332 keV using narrow beam transmission geometry. The photon beam was highly collimated and overall scatter acceptance angle was less than 3°. Our results have an uncertainty of less than 3%. These coefficients were then used to obtain the values of mean free path (mfp), effective atomic number and electron density. Good agreements have been observed between experimental and theoretical values of these parameters. From the studies of the obtained results it is reported here that from the shielding point of view the barium-borate-flyash glasses are better shields to γ-radiations in comparison to the standard radiation shielding concretes and also to the ordinary barium-borate glasses.     

Measurement of keV-neutron capture cross-sections and capture γ-ray spectra of Fe and Fe

The neutron capture cross-sections and the capture γ-ray spectra of ⁵⁶Fe and ⁵⁷Fe have been measured in the neutron energy range from 10 to 90 keV. Pulsed keV-neutrons were produced from the ⁷Li(p,n)⁷Be reaction by bombarding a lithium target with a 1.5-ns bunched proton beam from a 3 MV Pelletron accelerator. The incident neutron spectrum on the capture sample was measured using a time-of-flight method with a ⁶Li-glass detector. The capture γ-rays emitted from an iron or standard gold sample were detected with a large anti-Compton NaI(Tl) spectrometer. The capture yield of the iron or gold sample was obtained by applying a pulse-height weighting technique to the corresponding capture γ-ray pulse-height spectrum. The capture cross-sections of ^56,57Fe were derived with errors less than 5% using the standard capture cross-sections of ¹⁹⁷Au. The capture γ-ray spectra were obtained by unfolding the observed capture γ-ray pulse-height spectra. The present results for the capture cross-sections were compared with the previous measurements and the evaluated values of ENDF/B-VII.0 and JENDL-3.3. The Maxwellian-averaged capture cross-sections of ⁵⁶Fe and ⁵⁷Fe at 30 keV are derived as 12.22 ± 2.06 mb and 44.48 ± 7.56 mb, respectively.     

就地计数系统小推车车体屏蔽修正

介绍了应用152Eu面源对就地计数系统(ISOCS)小推车车体屏蔽修正的实验方法和计算方法。BE5030型HPGe探测器配带50mm-90°、50mm-30°或50mm-180°铅准直器,端面向下,垂直地面测量,探测器距地面58.2cm。得到了该测量条件下关注能量γ射线的小推车屏蔽修正因子。并通过最小二乘拟合得到屏蔽因子与γ射线能量的关系式,用以内插获得122～1408keV范围内任意γ射线的小推车车体屏蔽修正因子。     

环境放射性样品装量与γ射线能量的关系

用γ谱仪分析环境土壤样品的放射性活度时,需将样品装在一定大小的圆柱形塑料盒内,习惯上总是将样品盒装满,而不考虑待分析的放射性核素发射何种能量γ射线。本文提出了样品装量与待测γ射线能量有关联的装样方法,并用蒙特卡罗方法模拟计算了不同能量γ射线的探测效率与样品装量之间的关系,得到用HPGeγ谱仪分析²³⁸U、²³²Th、²²⁶Ra和⁴⁰K等放射性核素活度各自的最佳装样量。     

参数法测量放射性活度

用HPGe探测器替代传统4πβ-γ符合装置中的NaI（Tl）探测器,对γ射线进行精细测量。选取一组适当的γ射线进行符合或反符合测量,计算出较为准确的β效率,从而简单地得到待测核素的放射性活度。¹³³Ba和131I活度的实验测量结果表明,4πβ-γ（HPGe）参数法是1种准确、可靠的放射性活度测量方法。     

Technique for Radioactivity Measurement in Drum Package Waste by Using Scattered Gamma-Rays

An evaluation method for the radionuclide content in low level drum package waste by using scattered γ-rays has been investigated. Gamma-rays are counted by a detector after passing through a collimator having appropriate vertical and horizontal openings both for the segmented scan and for the average geometrical efficiency being almost independent of the source position. The attenuation of unscattered γ-rays is estimated from the intensity ratio of scattered rays to unscattered ones of the nuclide emitting the highest γ-ray energy in the drum. Satisfactory results were obtained in numerical simulations and basic experiments carried out using test equipment with a pure Ge detector and a rectangular collimator, and sample 200l drums, containing sealed ⁶⁰Co and ¹³⁷Cs sources, and having a uniform density of 2.2 g/cm³. The error of the evaluated content, which depended slightly on the activity distribution, was a maximum of about ±30%.     

Measurements of the Y(n,γ)Y cross-section in the neutron energy range of 13.5-14.6 MeV

The ⁸⁹Y(n,γ)^90mY cross-section has been measured at three neutron energy points between 13.5 and 14.6 MeV using the activation technique and a coaxial HPGe γ-ray detector. The data for the ⁸⁹Y(n,γ)^90mY cross-sections are reported to be 0.39 ± 0.02, 0.43 ± 0.02, and 0.38 ± 0.02 mb at 13.5 ± 0.2, 14.1 ± 0.1, and 14.6 ± 0.2 MeV incident neutron energies, respectively. The first data for the ⁸⁹Y(n,γ)^90mY reaction at neutron energy points of 13.5 and 14.1 MeV are presented. The natural high-purity Y₂O₃ powder was used as target material. The fast neutrons were produced by the T(d,n)⁴He reaction. Neutron energies were determined by the method of making cross-section ratios of ⁹⁰Zr(n,2n)^89m+gZr and ⁹³Nb(n,2n)^92mNb reactions, and the neutron fluencies were determined using the monitor reaction ⁹³Nb(n,2n)^92mNb. The results obtained are compared with existing data.     

Precise Measurement of the Gamma-ray Emission Probabilities for 116m In with Half-life of 54.15 min

The γ-ray emission probabilities for ^116mIn with half-life of 54.15 min have been measured by a 4πβ(pc)-γ(HPGe) coincidence apparatus using a live-timed two-dimensional data acquisition system. Eleven γ-ray peaks of ^116mIn were recognised and the uncertainties of the measured emission probabilities for principal γ-rays were found to be less than 1%. On the other hand, the relative intensities for 18 energy γ-rays were determined with improved uncertainties by an ordinary γ-ray spectrometer. The decay parameters were determined with uncertainties of approximately 1%using these values and the evaluated values of weak γ-ray intensities and the internal conversion coefficients.     

Reaction-yield dependence of the (γ, γ′) reaction of 238U on the target thickness

The dependence of the nuclear resonance fluorescence (NRF) yield on the target thickness was studied. To this end, an NRF experiment was performed on ²³⁸U using a laser Compton back-scattering (LCS) γ-ray beam at the High Intensity γ-ray Source facility at Duke University. Various thicknesses of depleted uranium targets were irradiated by an LCS γ-ray beam with an incident beam energy of ～2.475 MeV. The scattering NRF γ-rays were measured using an High-purity Germanium (HPGe) detector array positioned at scattering angles of 90° relative to the incident γ-beam. An analytical model for the NRF reaction yield (NRF RY model) is introduced to interpret the experimental data. Additionally, a Monte Carlo simulation using GEANT4 was performed to simulate the NRF interaction for a wide range of target thicknesses of the ²³⁸U. The measured NRF yield shows the saturation behavior. The results of both of the simulation and the analytical model can reproduce the saturation curve of the scattering NRF yield of ²³⁸U against the target thickness. In addition, we propose a method to deduce the precise integral cross section of the NRF reaction by fitting the NRF yield dependency on the target thickness without any absolute measurements.     

CeF3晶体伽玛能响及抗中子能力研究

用Monte Carlo和核物理理论分析的方法研究了CeF3晶体对γ射线的能量响应趋势,并通过实验测量了CeF3晶体与光电倍增管组合构成的闪烁探测器对不同能量的中子和γ射线的灵敏度。结果表明:CeF3晶体在0.3～0.9 MeV能区具有较平坦的γ能量响应曲线,较强的抗中子干扰能力。     

Albedo Component of Gamma-Ray Streaming through Straight Cylindrical Ducts

An experimental study was performed to investigate the effect of γ-ray streaming through cylindrical steel and lead ducts having various lengths and radii. In the experiment, ⁶⁰Co and ¹³⁷Cs point sources, and small sized detector (pulse dosimeter with plastic scintillator) was adopted, source and detector being located at the centers of opposite duct mouths. The albedo-to-direct component ratio is about 30% for steel ducts and 10% for lead at γ-ray energies of 1.25 and 0.661 MeV, with L/R ₀~10.

The measured results were compared with those calculated by the Monte Carlo method; they showed a good agreement. Consequently, the prediction of doses for straight cylindrical ducts having various length-to-radius ratios can be made by the procedures based on the Monte Carlo calculations.     

Resolution and sensitivity as a function of energy and incident geometry for germanium detectors

The use of modeling programs such as MCNP to predict the response of HPGe detectors is increasing in importance. Accurate simulation of germanium detectors to incident gamma rays relies on knowledge of the performance of the detector in different detector–source geometries. Two important performance parameters are the resolution and sensitivity. The resolution is the FWHM and FW.1M/FWHM ratio. The IEEE 325-1996 standard only specifies the FWHM measurement at one geometry and two energies. Nearly all measurements are made in a different geometry and at other energies. Other investigators [Specifications for Today’s Coaxial HPGe Detectors, 2001 ANS Annual Meeting, Milwaukee, WI; Metzger, private communication, see also: Radionuclide Depth Distribution by Collimated Spectroscopy, 2002 ANS Topical Meeting, Santa Fe, NM], have shown that the sensitivity and resolution change with position of the incident gamma ray on the front of the detector. Such variability has possible implications for the accuracy of peak shape and area determination, since the calibration is potentially a function of angle of incidence. To quantify the sensitivity and resolution variation as a function of energy and point of incidence, measurements have been made on several coaxial detectors of various crystal types and sizes in different source–detector geometries. The full-energy peaks from 59 keV to 2.6 MeV were used. The detectors were placed in a low-background shield to reduce any contribution from external sources. None of the detectors tested was a low-background type. The sources used were an ²⁴¹Am source, ⁶⁰Co source and a natural thorium oxide sample. The ²⁴¹Am 59 keV gamma rays were collimated by a 2 cm thick, 1 mm diameter lead collimator. Several gamma rays from the thorium source were used and collimated by a 10 cm thick and 2 mm diameter tungsten collimator. These collimated sources were used to collect spectra for the incident beam on the front and sides of the detectors. The peak widths were calculated using the methods outlined in IEEE 325-1996. Data are presented to show that the peak shape and sensitivity change with incident beam position and full peak energy.     

~(87)Kr γ射线发射几率的重新测定

在以往87Kr的测量实验中,壁效应校正和HPGe探测器效率刻度结果不确定度均较大。本工作针对存在的问题,改进了实验装置,准确进行了壁效应校正,用长度补偿法测得了放射性活度浓度为100.87(1±0.86%)Bq/mL;重新设计加工了能准确标定HPGe探测器效率的源盒,测得87Kr402.6keVγ射线的发射几率为49.46%(1±1.9%)。     

GEANT4 simulation of water volume fraction measurement in dehydrated crude oil

Online measurement of water volume fraction (WVF) in dehydrated crude oil is a difficult task due to very little water in dehydrated crude oil and high precision requirements. We presents a method to measure water volume fraction in dehydrated crude oil with γ-ray densitometry. The Monte Carlo computer simulation packet GEANT4 was used to analyze the WVF measuring sensitivity of the γ-ray densitometry at different γ-ray energies, and effects of temperature, pressure, salinity and oil components on WVF measurement. The results show that the γ-ray densitome-try has high sensitivity in γ-ray energy ranges of 16～25 keV, and it can distinguish WVF changes of 0.0005. The calculated WVF decreases about 0.0002 with 1 ℃ of temperature increase and they have approximately linear relation with temperature when water volume fraction remains the same. Effects of pressure, salinity and oil components on water volume fraction can be neglected. Experiments were done to analyze sensitivity of the γ-ray densitometry. The results, as compared with simulations, demonstrate that simulation method is reliable and it is feasible to gauge low water volume fraction using low energy γ-rays.     

Optimization of GEANT4 settings for Proton Pencil Beam Scanning simulations using GATE

This study reports the investigation of different GEANT4 settings for proton therapy applications in the context of Treatment Planning System comparisons. The GEANT4.9.2 release was used through the GATE platform. We focused on the Pencil Beam Scanning delivery technique, which allows for intensity modulated proton therapy applications. The most relevant options and parameters (range cut, step size, database binning) for the simulation that influence the dose deposition were investigated, in order to determine a robust, accurate and efficient simulation environment. In this perspective, simulations of depth-dose profiles and transverse profiles at different depths and energies between 100 and 230 MeV have been assessed against reference measurements in water and PMMA. These measurements were performed in Essen, Germany, with the IBA dedicated Pencil Beam Scanning system, using Bragg-peak chambers and radiochromic films. GEANT4 simulations were also compared to the PHITS.2.14 and MCNPX.2.5.0 Monte Carlo codes. Depth-dose simulations reached 0.3 mm range accuracy compared to NIST CSDA ranges, with a dose agreement of about 1% over a set of five different energies. The transverse profiles simulated using the different Monte Carlo codes showed discrepancies, with up to 15% difference in beam widening between GEANT4 and MCNPX in water. A 8% difference between the GEANT4 multiple scattering and single scattering algorithms was observed. The simulations showed the inability of reproducing the measured transverse dose spreading with depth in PMMA, corroborating the fact that GEANT4 underestimates the lateral dose spreading. GATE was found to be a very convenient simulation environment to perform this study. A reference physics-list and an optimized parameters-list have been proposed. Satisfactory agreement against depth-dose profiles measurements was obtained. The simulation of transverse profiles using different Monte Carlo codes showed significant deviations. This point is crucial for Pencil Beam Scanning delivery simulations and suggests that the GEANT4 multiple scattering algorithm should be revised.     

Cross section measurements for As isotope at neutron energies from 13.5 to 14.8 MeV

Cross sections which is relevant in research of neutron transmutation doping of some important semiconducting materials were measured at neutron energies from 13.5 to 14.8 MeV for the reactions ⁷⁵As(n, 2n)⁷⁴As, ⁷⁵As(n, p)^75m+gGe, ⁷⁵As(n, α)^72m+gGa by activation relative to the ²⁷Al(n, α)²⁴Na reaction. Measurements were carried out by γ-detection using a coaxial HPGe detector. Natural realgar (As₂S₂) powder of 99.9% purity was used as samples. Fast neutrons were produced by the T(d, n)⁴He reaction. The results obtained are compared with existing data.     

闪烁体耦合SiPM测量γ能谱的模拟研究

硅光电倍增管(Silicon photomultiplier,SiPM)是一种新型的光电探测器件,由工作在盖革模式下的雪崩二极管阵列组成。利用GEANT4蒙特卡罗软件包对LaBr_3:10%Ce~(3+)、Na I(TI)闪烁晶体耦合SiPM测量γ射线能谱进行了细致的模拟,通过单色光LED光源照射SiPM,得到SiPM自身暗电流噪声经电子学放大后,与集成的盖革雪崩二极管之间的间隙引起吸收光子涨落对能谱的展宽。对模拟得到的662 keVγ射线能量分辨率进行修正,最后与实验结果对比能够很好地符合,还得到了一组对应闪烁晶体本征能量分辨率的程序参数Pr,s。结果验证了模拟程序设置的闪烁晶体与封装材料光学参数的合理性与可靠性,为闪烁体探测器设计提供了一套开发工具。